Modelling study of divertor W leakage for different divertor conditions with Ne seeding in EAST tokamak

Abstract Sequential SOLPS-ITER and DIVIMP simulations are carried out for tungsten (W) edge transport during neon (Ne) injection in EAST, elucidating the pathway of W impurity leakage from the divertor to the core plasma under different dissipative divertor conditions. Divertor conditions from low-recycling to detachment are generated by modulating the Ne injection rate in the SOLPS simulation. With the drift velocities incorporated in DIVIMP, W transport under the drift effect is investigated. For low-density L-mode plasma conditions with favorable B t direction, the majority of W source originates from the outer divertor target and leaks upstream through the near-SOL E × B drift reversed region at both inner and outer divertors. The E × B drift is demonstrated to have a significant effect on W leakage and the effect diminishes with the increase of Ne injection rate. Compared to the D 2 injection cases, Ne injection helps to achieve a strong dissipative divertor condition at a much lower plasma density, resulting in a higher W leakage ability due to the smaller friction with the background plasma. For Ne injection cases under high-density H-mode conditions, W leaks mostly through the outer divertor region while the inner divertor is fully detached. Compared to the L-mode cases, the shorter power decay lengths in the scrap-off layer (SOL) of the H-mode cases result in smaller parallel E × B drift velocities especially in the middle and far SOL region. With the increase of the Ne injection rate, the decrease of the E × B drift in the middle SOL leads to a wider near-separatrix W leakage path. Therefore, a worse divertor W screening is expected, which is consistent with the previous published experimental observations (Ding et al 2022 Nucl. Mater. Energy 33 101250).

Authors

Institutions

Publication Details

Journal
Nuclear Fusion
Published
2024-10-02
DOI
https://doi.org/10.1088/1741-4326/ad8243
Citations
5
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
3.30

Funders

Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Modelling study of divertor W leakage for different divertor conditions with Ne seeding in EAST tokamak

Guozhang Jia, Hai Xie, Jin Guo, Guoliang Xu et al.
5 citations
Nuclear Fusion
Magnetic confinement fusion research
3.30
article

Modelling study of divertor W leakage for different divertor conditions with Ne seeding in EAST tokamak

Guozhang Jia, Hai Xie, Jin Guo, Guoliang Xu, Ran Hai, Rui Ding, Junling Chen, Dahuan Zhu, Rong Yan, Hang Si, Hui Wang
article en
5 citations

Abstract

Abstract Sequential SOLPS-ITER and DIVIMP simulations are carried out for tungsten (W) edge transport during neon (Ne) injection in EAST, elucidating the pathway of W impurity leakage from the divertor to the core plasma under different dissipative divertor conditions. Divertor conditions from low-recycling to detachment are generated by modulating the Ne injection rate in the SOLPS simulation. With the drift velocities incorporated in DIVIMP, W transport under the drift effect is investigated. For low-density L-mode plasma conditions with favorable B t direction, the majority of W source originates from the outer divertor target and leaks upstream through the near-SOL E × B drift reversed region at both inner and outer divertors. The E × B drift is demonstrated to have a significant effect on W leakage and the effect diminishes with the increase of Ne injection rate. Compared to the D 2 injection cases, Ne injection helps to achieve a strong dissipative divertor condition at a much lower plasma density, resulting in a higher W leakage ability due to the smaller friction with the background plasma. For Ne injection cases under high-density H-mode conditions, W leaks mostly through the outer divertor region while the inner divertor is fully detached. Compared to the L-mode cases, the shorter power decay lengths in the scrap-off layer (SOL) of the H-mode cases result in smaller parallel E × B drift velocities especially in the middle and far SOL region. With the increase of the Ne injection rate, the decrease of the E × B drift in the middle SOL leads to a wider near-separatrix W leakage path. Therefore, a worse divertor W screening is expected, which is consistent with the previous published experimental observations (Ding et al 2022 Nucl. Mater. Energy 33 101250).

Nuclear FusionVol. 64(12)
Chinese Academy of Sciences (CN), Dalian University of Technology (CN), Hefei Institutes of Physical Science (CN), Institute of Plasma Physics (CN)
National Natural Science Foundation of China
Openalex Percentile: Top 6%
Magnetic confinement fusion research
3.30
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.